F80 核仪器与核探测器综合 标准查询与下载

EJ/T 1051-1997 核仪器型号命名方法

Nomenclature for the type of nuclear instruments

ASTM C1344-97 用标准气体源质谱法进行六氟化铀的同位分析的标准试验方法

1.1 This test method covers the isotopic analysis of uranium hexafluoride (UF6) and may be used for the entire range of 235U isotopic compositions for which standards are available. This test method is adaptable to the determination of any uranium isotope. 1.2 This test method is applicable to the determination of the isotopic relationship between two UF6 samples. If the abundance of a specific isotope of one sample (the standard) is known, its abundance in the other can be determined. This test method is flexible in that the number of times a given material is admitted to the ion source may be adjusted to the minimum required for a specific precision level. 1.3 The sensitivity with which differences between two materials can be detected depends on the measuring system used, but ratio-measuring devices can generally read ratio-of-mol ratio differences as 0.0001. 1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific hazards statements are given in Section 7.

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single-Standard Gas Source Mass Spectrometer Method

ASTM E1893-97 为支持停工而进行的现场放射性评定用便携式放射性测量仪器的选择和使用的标准指南

1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from firther regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.

Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments in Support of Decommissioning

ASTM E1894-97(2002) 选择脉冲X射线源用的剂量测定系统的标准指南

Flash x-ray facilities provide intense bremsstrahlung radiation environments, usually in a single sub-microsecond pulse, which unfortunately, often fluctuates in amplitude, shape, and spectrum from shot to shot. Therefore, appropriate dosimetry must be fielded on every exposure to characterize the environment. These intense bremsstrahlung sources have a variety of applications which include the following: 5.1.1 Generation of x–ray and gamma–ray environments similar to that from a nuclear weapon burst. 5.1.2 Studies of the effects of x–rays and gamma rays on materials. 5.1.3 Studies of the effects of radiation on electronic devices such as transistors, diodes, and capacitors. 5.1.4 Vulnerability and survivability testing of military systems and components. 5.1.5 Computer code validation studies. This guide is written to assist the experimenter in selecting the needed dosimetry systems (often in an experiment not all radiation parameters must be measured) for use at pulsed x–ray facilities. This guide also provides a brief summary of the information on how to use each of the dosimetry systems. Other guides (see Section 3) provide more detailed information on selected dosimetry systems in radiation environments and should be consulted after an initial decision is made on the appropriate dosimetry system to use. There are many key parameters which describe a flash x-ray source, such as dose, dose rate, spectrum, pulse width, etc., such that typically no single dosimetry system can measure all the parameters simultaneously.1.1 This guide provides assistance in selecting and using dosimetry systems in flash x-ray experiments. Both dose and dose-rate techniques are described.1.2 Operating characteristics of flash x-ray sources are given, with emphasis on the spectrum of the photon output.1.3 Assistance is provided to relate the measured dose to the response of a device under test (DUT). The device is assumed to be a semiconductor electronic part or system.

Standard Guide for Selecting Dosimetry Systems for Application in Pulsed X-Ray Sources

ASTM E1894-97 选择脉冲X射线源用的剂量测定系统的标准指南

1.1 This guide provides assistance in selecting and using dosimetry systems in flash x-ray experiments. Both dose and dose-rate techniques are described. 1.2 Operating characteristics of flash x-ray sources are given, with emphasis on the spectrum of the photon output. 1.3 Assistance is provided to related the measured dose to the response of a device under test (DUT). The device is assumed to be a semiconductor electronic part or system.

Standard Guide for Selecting Dosimetry Systems for Application in Pulsed X-Ray Sources

IEEE N42.26-1997 辐射防护设备.监测设备.X和γ辐射的个人报警装置

Applies to devices used to give an indication of personal dose equivalent rate, from X and gamma radiations with energies from 60 keV to 1,5 MeV namely H(10). If the device is to be used for photon energies up to 10 MeV, for example at a nuclea

Radiation protection instrumentation - Monitoring equipment - Personal warning devices for X and gamma radiations

ASTM C1344-97(2003) 用标准气体源质谱法进行六氟化铀的同位分析的标准试验方法

Uranium hexafluoride is a basic material used to prepare nuclear reactor fuel. To be suitable for this purpose, the material must meet the criteria for isotopic composition. This test method is designed to determine whether the material meets the requirements described in Specifications C 787 and C 996. ASTM Committee C-26 Safeguards Statement: 5.2.1 The material (uranium hexafluoride) to which this test method applies is subject to the nuclear safeguards regulations governing its possession and use. The analytical procedure in this test method has been designated as technically acceptable for generating safeguards accountability data. 5.2.2 When used in conjunction with appropriate certified reference materials (CRMs), this procedure can demonstrate traceability to the national measurement base. However, adherence to this procedure does not automatically guarantee regulatory acceptance of the regulatory safeguards measurements. It remains the sole responsibility of the user of this test method to ensure that its application to safeguards has the approval of the proper regulatory authorities.1.1 This test method covers the isotopic analysis of uranium hexafluoride (UF6) and may be used for the entire range of 235U isotopic compositions for which standards are available.1.2 This test method is applicable to the determination of the isotopic relationship between two UF6 samples. If the abundance of a specific isotope of one sample (the standard) is known, its abundance in the other can be determined. This test method is flexible in that the number of times a given material is admitted to the ion source may be adjusted to the minimum required for a specified precision level.1.3 The sensitivity with which differences between two materials can be detected depends on the measuring system used, but ratio-measuring devices can generally read ratio-of-mol ratio differences as small as 0.0001.1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific hazards statements are given in Section 7.

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single-Standard Gas Source Mass Spectrometer Method

ASTM E1893-97(2003) 为支持停工而进行的现场放射性评定用便携式放射性测量仪器的选择和使用的标准指南

The purpose of this standard is to provide the user information and guidance for selecting and using instrumentation that will provide measurement results that can be compared to criteria for unrestricted use. Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient for making decisions regarding completion of decontamination and/or demolition/removal activities. Use of this standard will provide greater assurance that the measurements obtained will be technically and administratively sufficient to meet all applicable regulatory requirements for unrestricted release of a component for recycle or reuse, or for unrestricted release of a remaining surface or area at the completion of decommissioning activities.1.1 This standard provides recommendations on the selection and use of portable instrumentation that is responsive to levels of radiation that are close to natural background. These instruments are employed to detect the presence of residual radioactivity that is at, or below, the criteria for release from further regulatory control of a component to be salvaged or reused, or a surface remaining at the conclusion of decontamination and/or decommissioning.1.2 The choice of these instruments, their operating characteristics and the protocols by which they are calibrated and used will provide adequate assurance that the measurements of the residual radioactivity meet the requirements established for release from further regulatory control.1.3 This standard is applicable to the in situ measurement of radioactive emissions that include:1.3.1 alpha1.3.2 beta (electrons)1.3.3 gamma1.3.4 characteristic x-rays1.3.5 The measurement of neutron emissions is not included as part of this standard.1.4 This standard dose not address instrumentation used to assess residual radioactivity levels contained in air samples, surface contamination smears, bulk material removals, or half/whole body personnel monitors.1.5 This standard does not address records retention requirements for calibration, maintenance, etc. as these topics are considered in several of the referenced documents.

Standard Guide for Selection and Use of Portable Radiological Survey Instruments for Performing In Situ Radiological Assessments in Support of Decommissioning

IEC 61256:1996 辐射防护仪表 洗衣房放射污染监测用监测仪

This International Standard relates to assemblies that are used to monitor clothing (laundered) for radioactive contamination. It applies to monitoring that is performed after the clothing has been washed and prior to re-use to determine that the clothing is acceptable for use. This standard does not apply to clothing used outside the workplace. The object of this standard is to define minimum performance requirements and general test procedures for laundry monitors.

Radiation protection instrumentation - Installed monitors for the detection of radioactive contamination of laundry

EJ/T 1010-1996 α、β放射性气溶胶监测仪校准与氡子体补偿有效性的检验方法

Calibration of α and β radioactive aerosol monitors and testing methods for effectiveness of radon daughter compensation

EJ/T 1011-1996 固定式中子剂量当量率仪、报警装置与监测仪

Fixed neutron dose equivalent rate meter, alarm device and monitor

EJ/T 1019-1996 核电厂安全重要仪表通道响应时间试验

本标准规定了核电厂安全重要仪表通道响应时间特性现场测定的要求和方法。 本标准适用于传感器是测量压力或温度的安全重要仪表通道。

Response time test of instrument channel important to safety in nuclear power plant

IEC 61344:1996 辐射防护仪表 监测设备 X和γ射线辐射的个人报警装置

Applies to devices used to give an indication of personal dose equivalent rate, from X and gamma radiations with energies from 60 keV to 1,5 MeV namely H(10). If the device is to be used for photon energies up to 10 MeV, for example at a nuclea

Radiation protection instrumentation - Monitoring equipment - Personal warning devices for X and gamma radiations

IEC 61343:1996 核反应堆仪表 沸水反应堆(BWR) 堆芯充分冷却监测用反应容器的测量

Applies to the monitoring of adequate cooling within the core of a boiling light water reactor (BWR). Adequate cooling of the reactor core can be achieved only by maintaining sufficient coolant inventory in the core to remove the heat. Good international

Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core

ASTM E1819-96 核设备退役的环境监测计划标准指南

1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: 1- Development of an environmental baseline prior to commencement of decommissioning activities; 2- Determination of release paths from site activities and their associated exposure pathways in the environment; and 3- Selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing DD activities and the reuse of the facility or area for other purposes.

Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

ANSI N42.23-1996 放射性分析实验室的测量和相关仪器质量保证

The purpose of this standard is to provide a) Guidance for a national program for testing, accrediting, and monitoring of all types of radioassay laboratories b) Guidance for the minimum requirements necessary to maintain a viable service laboratory for

Measurement and Associated Instrumentation Quality Assurance for Radioassay Laboratories

ASTM E1819-96(2005) 核设备退役的环境监测计划标准指南

Use of this guide will ensure that the potential impact on the surrounding environment from planned decommissioning activities has been properly assessed. Use of this guide will ensure that the adequacy of environmental sampling has been assessed for location, frequency, analytical techniques, and media type to monitor the environment and to detect site-related releases and their impact.1.1 This guide covers the development or assessment of environmental monitoring plans for decommissioning nuclear facilities. This guide addresses: (1) development of an environmental baseline prior to commencement of decommissioning activities; ( 2) determination of release paths from site activities and their associated exposure pathways in the environment; and (3) selection of appropriate sampling locations and media to ensure that all exposure pathways in the environment are monitored appropriately. This guide also addresses the interfaces between the environmental monitoring plan and other planning documents for site decommissioning, such as radiation protection, site characterization, and waste management plans, and federal, state, and local environmental protection laws and guidance. This guide is applicable up to the point of completing DD activities and the reuse of the facility or area for other purposes.

Standard Guide for Environmental Monitoring Plans for Decommissioning of Nuclear Facilities

IEC 61452:1995 核仪器 放射性核素r射线发射率的测量 锗分光仪的校验和应用

Provides a basis for the routine calibration and use of germanium semiconductor detectors for the measurement of gamma-ray emission rates and thereby the activities of the radionuclides in a sample. It is primarily intended for routine analytical measure

Nuclear instrumentation - Measurement of gamma-ray emission rates of radionuclides - Calibration and use of germanium spectrometers

EJ/T 961-1995 离心机级联试验质量控制规范

Centrifuge cascade test quality control specification

ANSI N42.22-1995 可溯源到美国国家标准技术研究院(NIST)的放射源和相关仪器质量控制

Presents a mechanism for manufacturers to establish traceability of radionuclide sources that are certified for radionuclide activity; concentration; or alpha, beta, x-, or gamma-ray emission rate to the National Institute of Standards and Technology (NI

Traceability of Radioactive Sources to the National Institute of Standards and Technology (NIST) and Associated Instrument Quality Control